Results of four experimental heats run at the end of the G-5 contract in the National Carbon Company Clarksburg production furnaces.

Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.

The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.

From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."

The following report examines methods to determine uranium nitrate hexahydrate on pretreated hexone in the range of 0 to 40 g./l. by infrared absorption measurements.

Objective: "The observations summarized in the present report were made to determine the stability of ferrous and sulfamate ions and sulfamic acid in RA Column scrub solution (RAS) and in aqueous solution comparable to the RA Column feed tee composition (RAFS). Knowledge of the stability of the reducing agent (ferrous iron) is necessary to properly plan the method of preparation and introduction of this component into the RA system and to assure dependable and reproducible performance."

This report presents the final results from the investigation of the ratio of Pu-239 fission cross section to U-235 fission cross section. Three sets of plutonium and uranium foils were prepared at KAPL and were investigated to acquire the final results.

From summary: "The relative absorptions of X-rays by various substances are listed as a guide to the application of the X-ray photometric method in chemical analysis and to the estimation of interference by extraneous substances."

This report follows an investigation of a cargo truck found contaminated by various radioactive material on a routine trip from Arco, Idaho to the Hanford plant on May 8, 1952. The report analyzes the truck's route in an attempt to find the location of the contaminating region.

Summary: A method was found for determining calcium concentrations in TBP process streams in spite of serious interferences bysodium, ferrous, uranyl, sulfate, phosphate, and sulfamate ions as well as by TBP. The precision attainable varied from sample to sample, depending upon its composition. In general, errors of 20% or greater occurred. The smallest determinable amount of calcium was about 10 mg/1.

This report discusses the settling rates and properties of 101-U sludge when slurried with increasing amounts of synthetic supernatant.

From introduction: "In this report an attempt was made to summarize the results of recent research on the effective height of smoke stacks. In this summary attention is paid only to the case in which the density of the stack effluent is the same as that of the surrounding air."

From introduction: The present report describes further refinements of the apparatus and the method to meet a need for a sensitive determination of carbon in plutonium.

Report summarizing data from Purex tests for pulse column specifications. These test results were used to estimate pilot plant specifications.

The following report describes work carried out to investigate whether the Hanford IB column as designed in a previous report will decontaminate the uranium adequately from plutonium, particularly if there's any slowness in either the rate of reduction or transfer of the plutonium.

This report describes an improved infrared absorption method to analyze aqueous samples and TBP after extraction. The method described in the following pages is the carbon tetrachloride extraction method.

The following report provides data from corrosion tests meant to evaluate the performance of Type 3098Cb stainless steel in BiP04 process dissolver solution containing mercuric ion.

"The attached report summarizes the work performed in the establishment of an improved spectrographic method for determining iron in plutonium."

Field tests were conducted to measure short-period pollutant concentrations at several stack heights during conditions of marked atmospheric instability and low wind speeds. The source was a mechanical smoke generator located at the 185-ft level of a tower.

An addendum to report HW-30390 a additional power generation calculation for P, the rate of energy release, in kilowatts, was derived.

Metallographic examination of an irradiated powder metal uranium slug from PT-313-105-4M⁽¹⁾ was undertaken primarily as an evaluation of recently remotized metallographic equipment. It was, also, proposed to compare the grain size with values obtained ultrasonically on the same slug. It was further proposed to make a comparison, so far as limited data permitted, of post-irradiated powder metal uranium grain size with that to be expected from normal uranium similarly irradiated.

Graphite suffers radiation damage when exposed to high energy particles. Many of its physical and chemical properties are changed. One of the effects which is easily measured is an increase in the interlayer or C₀ distance of the crystal lattice. This has been attributed to the displacement of atoms or groups of atoms into interstitial positions of the lattice forcing the planes apart. The C₀ expansion may be annealed out by heating the damaged crystal to high temperatures. This paper deals with the rate of annealing of C₀ damage at several constant temperatures.

Values of copper tubing pressure drops as determined by test for low flow rates of air, helium, carbon dioxide and water are contained herein. The work was performed in order to provide original data, useful for design work at Hanford Atomic Products Operation, and not available in any known handbook or other publication.

Reactivity measurements conducted in the Hanford Test Pile are interpreted to yield resonance integrals for uranium, uranium oxide, thorium and thorium oxide. The experiments were made using cadmium filters and are discussed in terms of the multiplication factor of the Hanford Test Pile.